ML16068A440

Core Operating Limits Report for Cycle 18 Operation, Revision 0

ML16068A440
Person / Time
Site:	Browns Ferry  (DPR-068)
Issue date:	03/08/2016
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF3C18, Rev. 0
Download: ML16068A440 (14)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 8, 2016 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296 Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report for Cycle 18 Operation, Revision 0 In accordance with the requirements of Technical Specification (TS) 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN),

Unit 3, Cycle 18, Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin Limit in support of fuel loading for Cycle 18 (Mode 3, 4, and 5 operation). A revision to the COLR will be issued prior to Cycle 18 startup covering all Modes of operation (Modes 1 through 5).

There are no new commitments contained in this letter. If you have any questions please contact Jamie L. Paul at (256) 729-2636.

Enclosure:

Core Operating Limits Report, (105% OL TP), for Cycle 18 Operation, TVA-COLR-BF3C18, Revision 0 cc: (w/ Enclosure)

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 18 Operation, TVA-COLR-BF3C18, Revision 0 (See Attached)

[i!/ilNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga, TN 37402 EDMS L32 160304 800 QA Document BFE-4008, Revision 0 Browns Ferry Unit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

TV A-COLR-BF3C18 Revision 0 (Final)

(Revision Log, Page v)

March 2016 Prepared:~ a u T. W. Eichenberg, Sr. Specialist Verified: ~

Approved: /r( &

Date:

s/~ I

~

Date: _3 /t_b ____ /t_6_

3/d1~

Date: _____

G. C. Storey, rvJ'anager/ BWR Fuel Engineering Reviewed: ~

Date: _3_A_

~ _

/,__,

/~----

D~~anager, Reactor Engineering Approved:

Date: _3_~_c_\\_

\\ -~-

Chairman, PORC Approved:

~ - 7 )~

Date: _____

Plant Manager

li!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table of Contents EDMS: L32160304 800 Date: March 6, 2016 Total Number of Pages= 12 (including review cover sheet)

List of Tables............................................................................................................................. iii List of Figures............................................................................................................................ iv Revision Log............................................................................................................................... v Nomenclature............................................................................................................................ vi References.............................................................................................................................. viii 1

Introduction........................................................................................................................ 1*

1.1 Purpose....................................................................................................... ~............... 1 1.2 Scope.......................................................................................................................... 1 1.3 Fuel Loading................................................................................................................ 1 1.4 Acceptability................................................................................................................ 1 2

Shutdown Margin Limit....................................... :............................................................... 3 BrO'MlS Feny Unit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

Page ii lVA-COLR-BF3C18, Revision 0

li!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Tables EDMS: L32 160304 800 Date: March 6, 2016 Nuclear Fuel Types.................................................................................................................... 2 BroM1s Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Fina~

Page iii 1VA-COLR-BF3C18, Revision 0

[i!/i] NPG None BrCM11S Ferry Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Figures EDMS: L32 160304 800 Date: March 6, 2016 Page iv lVA-COLR-BF3C18, Revision 0

U!Jil NPG Number Page Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Revision Log Description 0-RO All New document.

8roM1s Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

EDMS: L32 160304 800 Date: March 6, 2016 Page v TVA-COLR-8F3C18, Revision 0

fi!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 APLHGR APRM AREVA NP BOC BSP BWR CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM EOC EOCLB EOOS FFTR FFWTR FHOOS ft GNF GWd HTSP ICA ICF IS kW LCO LFWH LHGRFAC LPRM LRNB MAPFAC MCPR Nomenclature Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)

Beginning of Cycle Backup Stability Protection Boiling Water Reactor Core Average Exposure Coast Down Core Monitoring System Software Core Operating Limits Report Critical Power Ratio Control Rod Withdrawal Error Cold SOM Delta CPR over Initial CPR vs. Oscillation Magnitude End of Cycle End-of-Cycle Licensing Basis Equipment OOS Final Feedwater Temperature Reduction Final Feedwater Temperature Reduction Feedwater Heaters OOS Foot: english unit of measure for length Vendor (General Electric, Global Nuclear Fuels)

Giga Watt Day High TSP Interim Corrective Action Increased Core Flow (beyond rated)

In-Service kilo watt: SI unit of measure for power.

License Condition of Operation Loss of Feedwater Heating LHGR Multiplier (Power or Flow dependent)

Low Power Range Monitor Generator Load Reject, No Bypass MAPLHGR multiplier (Power or Flow dependent)

Minimum CPR l3roMls Feny Um 3 Cycle 18 Core OperatirlJ Limits Report, (105% OL TP)

(Final)

EDMS: L32160304 800 Date: March 6, 2016 Page vi 1VA-COLR-BF3C18, Revision 0

fiENPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanoog*a TN 37402 MSRV MSRVOOS MTU MWd/MTU NEOC NRC NSS NTSP OLM CPR oos OPRM oss Moisture Separator Reheater Valve MSRV OOS Metric Ton Uranium Mega Watt Day per Metric Ton Uranium Near EOC United States Nuclear Regulatory Commission Nominal Scram Speed Nominal TSP MCPR Operating Limit Out-Of-Service Oscillation Power Range Monitor Optimum Scram Speed Period Based Detection Algorithm EDMS: L32160304 800 Date: March 6, 2016 PBDA Pbypass PLU PLUOOS PRNM Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed Power Load Unbalance RBM RC PO OS RPS RPT RPTOOS SOM SLM CPR SLO TBV TBVIS TBVOOS TIP TIPOOS TLO TSP TSSS TVA PLU OOS Power Range Neutron Monitor Rod Block Monitor Recirculation Pump OOS (SLO)

Reactor Protection System Recirculation Pump Trip RPTOOS Shutdown Margin MCPR Safety Limit Single Loop Operation Turbine Bypass Valve TBVIS Turbine Bypass Valves OOS Transversing In-core Probe TIP OOS Two Loop Operation Trip Setpoint Technical Specification Scram Speed Tennessee Valley Authority l3roM1s Ferry Urn 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(FinaQ Page vii 1VA-COLR-BF3C18, Revision 0

fim NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 References EDMS: L32 160304 800 Date: March 6, 2016

1.

ANP-3433P, Revision 0, Browns Ferry Unit 3 Cycle 18 Fuel Cycle Design, AREVA Inc., December 2015.

Methodology References

2.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

3.

XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

4.

EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

5.

ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

6.

XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

7.

XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

8.

EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

9.

XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

1 o.

XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

11.

ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP Inc., June 2011.

12.

ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced* Nuclear Fuels Corporation, August 1990.

13.

ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005.

14.

EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP Inc.,

September 2009.

8roM1s Ferry Urn 3 Cycle 18 Core OperatillJ Limits Report, (105% OL TP)

(Final)

Page viii 1VA-COLR-BF3C18, Revisioo 0

[i!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 EDMS: L32 160304 800 Date: March 6, 2016

15.

EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001, as supplemented by the site specific approval in NRC safety evaluations dated February 15, 2013 and July 31, 2014.

16.

EMF-2292(P)(A) Revision 0, ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

17.

EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18.

BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP Inc., May 2008.

19.

BAW-10247PA, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP Inc., April 2008.

20.

ANP-10298PA, Revision 0, ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP Inc., March 2010.

21.

ANP-3140(P), Revision 0, Browns Ferry Units 1, 2 ~ and 3 Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP Inc.,

August 2012.

BrCM11S Feny Urn 3 Cyde 18 Core Operatirg Limits Report, (105% OL TP)

(Final)

Page ix 1VA-COLR-BF3C18, Revisioo 0

fim NPG 1 Introduction Reactor Engineering and Fuels - BWRFE 1101 Market Street. Chattanooga TN 37402 EDMS: L32160304 800 Date: March 6, 2016 In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document may be provided, upon final approval, to the NRC.

1.2 Scope This version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 3, 4 & 5 operation of the unit. Expanding operation for MODE 1, and 2 will be addressed in a future COLR revision. This document will discuss the following areas:

)o;>-

Shutdown Margin (SOM) Limit (Technical Specification 3.1.1)

Applicability: All Modes 1.3 Fuel Loading The core will contain previously exposed AREVA NP, Inc., ATRIUM--10 fuel, along with fresh ATRIUM-10XM. Nuclear fuel types used in the core loading are shown in Table 1.1. The planned outage will consist of a full core off-load for maintenance. The final core loading was evaluated for BOC cold shutdown margin performance as documented per Reference 1.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through* 21.

BroMls Ferry Urit 3 Cycle 18 Core Operating Limils Report, (105% OL TP)

(Final)

Page 1 TVA-COLR-BF3C18, Revision 0

EDMS: L32 160304 800 fimNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 6, 2016 Table 1.1 Nuclear Fuel Types*

Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT)

(Ranqe)

ATRIUM-10 A10-3440B-11 GVBO-FCE 16 70 12 FCE002-FCE144 ATRIUM-10 A10-3826B-13GV80-FCE 16 39 13 FCE145-FCE188 ATRIUM-10 A 10-4075B-13GV80-FCE 16 15 14 FCE190-FCE235 ATRIUM-10 A10-4081B-12GV80-FCE 16 48 15 FCE237-FCE284 ATRIUM-10 A10-3849B-13GV80-FCF 17 176 16 FCF301-FCF476 ATRIUM-10 A10-3882B-10GV70-FCF 17 40 17 FCF477-FCF516 ATRIUM-10 A10-4116B-12GV70-FCF 17 72 18 FCF517-FCF588 ATRIUM-1 OXM XMLC-41058-11 GV70-FCG 18 72 19 FCG601-FCG672 ATRIUM-10XM XMLC-4096B-12GV80-FCG 18 136 20 FCG673-FCG808 ATRIUM-10XM XMLC-4055B-13GV70-FCG 18 96 21 FCG809-FCG904

• The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.

8roMls Ferry Urn 3 Cycle 18 Core Operating Limits Report, ( 105% OL TP)

(Final)

Page 2 1VA-COLR-BF3C18, Revision 0

(l!i] NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2 Shutdown Margin Limit (Technical Specification 3.1.1)

EDMS: L32160304 800 Date: March 6, 2016 Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:

Br<MnS Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(FinaQ SOM

> 0.38% dk/k Page 3 1VA-COLR-BF3C18, Revisioo 0

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 8, 2016 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296 Browns Ferry Nuclear Plant, Unit 3 Core Operating Limits Report for Cycle 18 Operation, Revision 0 In accordance with the requirements of Technical Specification (TS) 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN),

Unit 3, Cycle 18, Core Operating Limits Report (COLR), Revision 0. This Unit 3 COLR was issued as an interim measure to include Shutdown Margin Limit in support of fuel loading for Cycle 18 (Mode 3, 4, and 5 operation). A revision to the COLR will be issued prior to Cycle 18 startup covering all Modes of operation (Modes 1 through 5).

There are no new commitments contained in this letter. If you have any questions please contact Jamie L. Paul at (256) 729-2636.

Enclosure:

Core Operating Limits Report, (105% OL TP), for Cycle 18 Operation, TVA-COLR-BF3C18, Revision 0 cc: (w/ Enclosure)

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Core Operating Limits Report, (105% OLTP), for Cycle 18 Operation, TVA-COLR-BF3C18, Revision 0 (See Attached)

[i!/ilNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga, TN 37402 EDMS L32 160304 800 QA Document BFE-4008, Revision 0 Browns Ferry Unit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

TV A-COLR-BF3C18 Revision 0 (Final)

(Revision Log, Page v)

March 2016 Prepared:~ a u T. W. Eichenberg, Sr. Specialist Verified: ~

Approved: /r( &

Date:

s/~ I

~

Date: _3 /t_b ____ /t_6_

3/d1~

Date: _____

G. C. Storey, rvJ'anager/ BWR Fuel Engineering Reviewed: ~

Date: _3_A_

~ _

/,__,

/~----

D~~anager, Reactor Engineering Approved:

Date: _3_~_c_\\_

\\ -~-

Chairman, PORC Approved:

~ - 7 )~

Date: _____

Plant Manager

li!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Table of Contents EDMS: L32160304 800 Date: March 6, 2016 Total Number of Pages= 12 (including review cover sheet)

List of Tables............................................................................................................................. iii List of Figures............................................................................................................................ iv Revision Log............................................................................................................................... v Nomenclature............................................................................................................................ vi References.............................................................................................................................. viii 1

Introduction........................................................................................................................ 1*

1.1 Purpose....................................................................................................... ~............... 1 1.2 Scope.......................................................................................................................... 1 1.3 Fuel Loading................................................................................................................ 1 1.4 Acceptability................................................................................................................ 1 2

Shutdown Margin Limit....................................... :............................................................... 3 BrO'MlS Feny Unit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

Page ii lVA-COLR-BF3C18, Revision 0

li!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Tables EDMS: L32 160304 800 Date: March 6, 2016 Nuclear Fuel Types.................................................................................................................... 2 BroM1s Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Fina~

Page iii 1VA-COLR-BF3C18, Revision 0

[i!/i] NPG None BrCM11S Ferry Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 List of Figures EDMS: L32 160304 800 Date: March 6, 2016 Page iv lVA-COLR-BF3C18, Revision 0

U!Jil NPG Number Page Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Revision Log Description 0-RO All New document.

8roM1s Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(Final)

EDMS: L32 160304 800 Date: March 6, 2016 Page v TVA-COLR-8F3C18, Revision 0

fi!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 APLHGR APRM AREVA NP BOC BSP BWR CAVEX CD CMSS COLR CPR CRWE CSDM DIVOM EOC EOCLB EOOS FFTR FFWTR FHOOS ft GNF GWd HTSP ICA ICF IS kW LCO LFWH LHGRFAC LPRM LRNB MAPFAC MCPR Nomenclature Average Planar LHGR Average Power Range Monitor Vendor (Framatome, Siemens)

Beginning of Cycle Backup Stability Protection Boiling Water Reactor Core Average Exposure Coast Down Core Monitoring System Software Core Operating Limits Report Critical Power Ratio Control Rod Withdrawal Error Cold SOM Delta CPR over Initial CPR vs. Oscillation Magnitude End of Cycle End-of-Cycle Licensing Basis Equipment OOS Final Feedwater Temperature Reduction Final Feedwater Temperature Reduction Feedwater Heaters OOS Foot: english unit of measure for length Vendor (General Electric, Global Nuclear Fuels)

Giga Watt Day High TSP Interim Corrective Action Increased Core Flow (beyond rated)

In-Service kilo watt: SI unit of measure for power.

License Condition of Operation Loss of Feedwater Heating LHGR Multiplier (Power or Flow dependent)

Low Power Range Monitor Generator Load Reject, No Bypass MAPLHGR multiplier (Power or Flow dependent)

Minimum CPR l3roMls Feny Um 3 Cycle 18 Core OperatirlJ Limits Report, (105% OL TP)

(Final)

EDMS: L32160304 800 Date: March 6, 2016 Page vi 1VA-COLR-BF3C18, Revision 0

fiENPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanoog*a TN 37402 MSRV MSRVOOS MTU MWd/MTU NEOC NRC NSS NTSP OLM CPR oos OPRM oss Moisture Separator Reheater Valve MSRV OOS Metric Ton Uranium Mega Watt Day per Metric Ton Uranium Near EOC United States Nuclear Regulatory Commission Nominal Scram Speed Nominal TSP MCPR Operating Limit Out-Of-Service Oscillation Power Range Monitor Optimum Scram Speed Period Based Detection Algorithm EDMS: L32160304 800 Date: March 6, 2016 PBDA Pbypass PLU PLUOOS PRNM Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed Power Load Unbalance RBM RC PO OS RPS RPT RPTOOS SOM SLM CPR SLO TBV TBVIS TBVOOS TIP TIPOOS TLO TSP TSSS TVA PLU OOS Power Range Neutron Monitor Rod Block Monitor Recirculation Pump OOS (SLO)

Reactor Protection System Recirculation Pump Trip RPTOOS Shutdown Margin MCPR Safety Limit Single Loop Operation Turbine Bypass Valve TBVIS Turbine Bypass Valves OOS Transversing In-core Probe TIP OOS Two Loop Operation Trip Setpoint Technical Specification Scram Speed Tennessee Valley Authority l3roM1s Ferry Urn 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(FinaQ Page vii 1VA-COLR-BF3C18, Revision 0

fim NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 References EDMS: L32 160304 800 Date: March 6, 2016

1.

ANP-3433P, Revision 0, Browns Ferry Unit 3 Cycle 18 Fuel Cycle Design, AREVA Inc., December 2015.

Methodology References

2.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

3.

XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

4.

EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

5.

ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

6.

XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

7.

XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

8.

EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

9.

XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

1 o.

XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

11.

ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP Inc., June 2011.

12.

ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced* Nuclear Fuels Corporation, August 1990.

13.

ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005.

14.

EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP Inc.,

September 2009.

8roM1s Ferry Urn 3 Cycle 18 Core OperatillJ Limits Report, (105% OL TP)

(Final)

Page viii 1VA-COLR-BF3C18, Revisioo 0

[i!/il NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 EDMS: L32 160304 800 Date: March 6, 2016

15.

EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001, as supplemented by the site specific approval in NRC safety evaluations dated February 15, 2013 and July 31, 2014.

16.

EMF-2292(P)(A) Revision 0, ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

17.

EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18.

BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP Inc., May 2008.

19.

BAW-10247PA, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP Inc., April 2008.

20.

ANP-10298PA, Revision 0, ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP Inc., March 2010.

21.

ANP-3140(P), Revision 0, Browns Ferry Units 1, 2 ~ and 3 Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP Inc.,

August 2012.

BrCM11S Feny Urn 3 Cyde 18 Core Operatirg Limits Report, (105% OL TP)

(Final)

Page ix 1VA-COLR-BF3C18, Revisioo 0

fim NPG 1 Introduction Reactor Engineering and Fuels - BWRFE 1101 Market Street. Chattanooga TN 37402 EDMS: L32160304 800 Date: March 6, 2016 In anticipation of cycle startup, it is necessary to describe the expected limits of operation.

1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document may be provided, upon final approval, to the NRC.

1.2 Scope This version of the COLR is specifically intended to support the refueling outage. Consequently, this document only covers MODE 3, 4 & 5 operation of the unit. Expanding operation for MODE 1, and 2 will be addressed in a future COLR revision. This document will discuss the following areas:

)o;>-

Shutdown Margin (SOM) Limit (Technical Specification 3.1.1)

Applicability: All Modes 1.3 Fuel Loading The core will contain previously exposed AREVA NP, Inc., ATRIUM--10 fuel, along with fresh ATRIUM-10XM. Nuclear fuel types used in the core loading are shown in Table 1.1. The planned outage will consist of a full core off-load for maintenance. The final core loading was evaluated for BOC cold shutdown margin performance as documented per Reference 1.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 2 through* 21.

BroMls Ferry Urit 3 Cycle 18 Core Operating Limils Report, (105% OL TP)

(Final)

Page 1 TVA-COLR-BF3C18, Revision 0

EDMS: L32 160304 800 fimNPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: March 6, 2016 Table 1.1 Nuclear Fuel Types*

Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT)

(Ranqe)

ATRIUM-10 A10-3440B-11 GVBO-FCE 16 70 12 FCE002-FCE144 ATRIUM-10 A10-3826B-13GV80-FCE 16 39 13 FCE145-FCE188 ATRIUM-10 A 10-4075B-13GV80-FCE 16 15 14 FCE190-FCE235 ATRIUM-10 A10-4081B-12GV80-FCE 16 48 15 FCE237-FCE284 ATRIUM-10 A10-3849B-13GV80-FCF 17 176 16 FCF301-FCF476 ATRIUM-10 A10-3882B-10GV70-FCF 17 40 17 FCF477-FCF516 ATRIUM-10 A10-4116B-12GV70-FCF 17 72 18 FCF517-FCF588 ATRIUM-1 OXM XMLC-41058-11 GV70-FCG 18 72 19 FCG601-FCG672 ATRIUM-10XM XMLC-4096B-12GV80-FCG 18 136 20 FCG673-FCG808 ATRIUM-10XM XMLC-4055B-13GV70-FCG 18 96 21 FCG809-FCG904

• The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.

8roMls Ferry Urn 3 Cycle 18 Core Operating Limits Report, ( 105% OL TP)

(Final)

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(l!i] NPG Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 2 Shutdown Margin Limit (Technical Specification 3.1.1)

EDMS: L32160304 800 Date: March 6, 2016 Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:

Br<MnS Feny Urit 3 Cycle 18 Core Operating Limits Report, (105% OL TP)

(FinaQ SOM

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